ND-21-0275, Vogtie Electric Generating Plant, Unit 3 - ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii (Index Number 348)

Vogtie Electric Generating Plant, Unit 3 - ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii (Index Number 348)

ML21081A096
Person / Time
Site:	Vogtle
Issue date:	03/19/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.3.05.03b.iii, ND-21-0275
Download: ML21081A096 (7)

Text

Sk. Southern Nuclear Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tei MAR I 9 2021 Docket Nos.: 52-025 ND-21-0275 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii [Index Number 3481 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC)of the completion of Vogtie Electric Generating Plant(VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.05.03b.iii [Index Number 348]. This ITAAC verified that the cask handling crane can lift, and hold rated loads and does not move over the spent fuel pool. The closure process for this ITAAC is based on the guidance described in NEI-08-01,"Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company(SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs D^ector Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of 2.3.05.03b.iii [Index Number 348]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-21-0275 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission Ms. M. Bailey (w/o enclosures)

Mr. M. King Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. E. Davidson Mr. T. Fanelli Mr. S. Rose Ms. K. McCurry Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-21-0275 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0275 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-21-0275 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.05.03b.iii [Index Number 348]

U.S. Nuclear Regulatory Commission ND-21-0275 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 3.b) The cask handling crane is single failure proof.

4. The cask handling crane cannot move over the spent fuel pool.

Inspections. Tests. Analvses ii) Testing of the cask handling crane is performed.

iii) Testing of the cask handling crane is performed.

Testing of the cask handling crane is performed.

Acceptance Criteria ii) The cask handling crane shall be static load tested to 125% of the rated load.

iii) The cask handling crane shall lift a test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.

The cask handling crane does not move over the spent fuel pool.

ITAAC Determination Basis Multiple ITAAC are performed to verify that the cask handling crane is single failure proof and cannot move over the spent fuel pool. This ITAAC performed static load testing to verify the cask handling crane main and auxiliary hoists can support 125% of the rated load, a lift test of a load that is 100% of the cask handling crane main and auxiliary hoist's rated load, including lowering, stopping and holding the test load, and testing of the cask handling crane to demonstrate it does not move over the spent fuel pool.

ii) The cask handling crane shall be static load tested to 125% of the rated load.

The cask handling crane main hoist 125% static load test was performed in accordance with Unit 3 site acceptance test procedure SV3-MH02-VTP-002(Reference 1) with a load equal to 125%

(+5%/-0%) of the cask handling crane main hoist rated load. This testing was performed as required by NUREG-0554 Section 8.2(Reference 2) in accordance with ASME NOG-1 (Reference 3). The main hoist was tested and visually observed to exhibit no drift downward after stopping and holding the test load. The load was successfully supported under these conditions.

Similarly, the cask handling crane auxiliary hoist was static load tested using Reference 1 with a load equal to 125%(+5%/-0%) of the cask handling crane auxiliary hoist rated load. The auxiliary hoist was tested and visually observed to exhibit no drift downward after stopping and holding the test load. The load was successfully supported under these conditions.

U.S. Nuclear Regulatory Commission ND-21-0275 Enclosure Page 3 of 4 The Unit 3 site acceptance test procedure SV3-MH02-VTP-002 confirmed that the cask handling crane main and auxiliary hoists were static load tested to 125% of the cask handling crane main and auxiliary hoist's rated load.

ill) The cask handling crane shall lift a test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.

The cask handling crane main hoist 100% load test was performed in accordance with Unit 3 site acceptance test SV3-MH02-VTP-002(Reference 1) with a load that is 100% (+5%/-0%) of the cask handling crane main hoist rated load. This test was performed as required by NUREG-0554 Section 8.2 (Reference 2) and was performed after the cask handling crane's static load test to 125% of rated load. The main hoist was tested and visually observed to exhibit no drift downward after lowering, stopping and holding the test load. The load was successfully supported under these conditions.

Similarly, the cask handling crane auxiliary hoist was 100% load tested using Reference 1 with a load equal to 100%(+5%/-0%) of the cask handling crane auxiliary hoist rated load. The auxiliary hoist was tested and visually observed to exhibit no drift downward after lowering, stopping and holding the test load. The load was successfully supported under these conditions.

The Unit 3 site acceptance test procedure SV3-MH02-VTP-002 documented and confirmed that the cask handling crane main and auxiliary hoists were load tested to 100% of the cask handling crane main and auxiliary hoist's rated load, including lowering, stopping and holding the test load.

The cask handling crane does not move over the spent fuel pool.

The cask handling crane test was performed to demonstrate that the crane does not move over the spent fuel pool in accordance with Unit 3 site acceptance test procedure SV3-MH02-VTP-002 (Reference 1).

This test was performed during the cask handling crane operational testing. During this test, the crane was operated by running the bridge into the bridge limit switch at full speed to verify it came to a complete stop before it engaged the mechanical stop, which is located prior to traveling over the spent fuel pool. Performance of the Unit 3 site acceptance test procedure SV3-MH02-VTP-002 documented and confirmed that the cask handling crane does not move over the spent fuel pool.

The completed site acceptance test results were compared to the ITAAC acceptance criteria and documented in ITAAC Technical Report SV3-MHS-ITR-800348 (Reference 4). The results demonstrated that the ITAAC acceptance criteria were met.

References 1 through 4 are available for NRC inspection as well as the Unit 3 ITAAC Completion Package (Reference 5).

Please note: Terminology used to describe the cask handling crane in the Uncompleted ITAAC Notification (UIN), ADAMS No: ML19170A326, has been corrected. The word "trolley" was replaced by "bridge" in the ITAAC Determination Basis section that describes the method employed to verify the cask handling crane does not move over the spent fuel pool.

U.S. Nuclear Regulatory Commission ND-21-0275 Enclosure Page 4 of 4 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.05.03b.ill (Reference 5)and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.05.03b.iii was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available for NRC Inspection)

1. SV3-MH02-VTP-002, Rev. 1,"Domestic AP1000 Cask Crane Site Acceptance Tesf

2. NUREG-0554,"Single-Failure-Proof Cranes for Nuclear Power Plants"

3. ASME NOG-1-1998,"Rules for Construction of Overhead and Gantry Cranes(Top Running Bridge, Multiple Girder)"

4. SV3-MHS-ITR-800348, Rev. 0,"Unit 3 Recorded Results of Cask Handling Crane Load Tests:

ITAAC 2.3.05.03b.iii, NRC Index 348"

5. 2.3.05.03b.iii-U3-CP-Rev0, ITAAC Completion Package